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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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July 2025
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Kyle Carberry, Bojan Petrovic
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 409-435
Research Article | doi.org/10.1080/00295450.2023.2229181
Articles are hosted by Taylor and Francis Online.
The research presented herein outlines a comprehensive process for characterizing the major radiological source terms necessary for radiation protection and licensing activities that one would expect in a liquid-fueled molten salt reactor. This process leverages organic simulation tools in the SCALE modeling and simulation code suite to provide an “off-the-shelf” solution for shielding assessments of this reactor type. Ultimately, this source development process is applied to a representative molten salt reactor system to assess the impact of ex-core source terms on shielding in varying operating conditions. The results of the analysis determined that while the prompt core source is the major dose contributor outside the radiological shielding, specific ex-core features, such as the primary salt loop components and configuration, can have an appreciable dose impact, and thus must be accounted for.